Event Notification Report for October 18, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/17/2011 - 10/18/2011
EVENT NUMBERS
47349473504735147352
Power Reactor
Event Number: 47349
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: JOSE A VASQUEZ
HQ OPS Officer: DONALD NORWOOD
Region: 2 State: FL
Unit: [3] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: JOSE A VASQUEZ
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/18/2011
Notification Time: 03:20 [ET]
Event Date: 10/18/2011
Event Time: 00:56 [EDT]
Last Update Date: 10/18/2011
Notification Time: 03:20 [ET]
Event Date: 10/18/2011
Event Time: 00:56 [EDT]
Last Update Date: 10/18/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
MARK LESSER (R2DO)
MARK LESSER (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 55 | Power Operation | 55 | Power Operation |
| 4 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION DUE TO WASTE WATER SPILL
"This is a four (4) hour Non-Emergency notification to the NRC Operations Center for a notification to other government agency in accordance with 10CFR50.72(b)(2)(xi).
"On 10/18/2011 at 0056 EDT, the Miami-Dade County Department of Environmental Resource Management (DERM) was notified of a spill of approximately 50 gallons of waste water (ash-water sluice) from Turkey Point Units 1 and 2 fossil power plants. This spill is not related to Turkey Point Units 3 and 4 nuclear power plant operations."
The licensee notified the NRC Resident Inspector.
"This is a four (4) hour Non-Emergency notification to the NRC Operations Center for a notification to other government agency in accordance with 10CFR50.72(b)(2)(xi).
"On 10/18/2011 at 0056 EDT, the Miami-Dade County Department of Environmental Resource Management (DERM) was notified of a spill of approximately 50 gallons of waste water (ash-water sluice) from Turkey Point Units 1 and 2 fossil power plants. This spill is not related to Turkey Point Units 3 and 4 nuclear power plant operations."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 47350
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: BEN WESCOT
HQ OPS Officer: JOE O'HARA
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: BEN WESCOT
HQ OPS Officer: JOE O'HARA
Notification Date: 10/18/2011
Notification Time: 05:59 [ET]
Event Date: 10/18/2011
Event Time: 04:50 [CDT]
Last Update Date: 10/18/2011
Notification Time: 05:59 [ET]
Event Date: 10/18/2011
Event Time: 04:50 [CDT]
Last Update Date: 10/18/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
ROBERT DALEY (R3DO)
ROBERT DALEY (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
TECHNICAL SUPPORT CENTER EMERGENCY DIESEL GENERATOR OUT OF SERVICE
"At 0450 (CDT), on October 18, 2011, the Duane Arnold Energy Center (DAEC) Technical Support Center (TSC) Emergency Diesel Generator (EDG) was removed from service for preplanned maintenance. The expected duration of the maintenance is 12 hours. Normal power to the TSC will be available for the duration of the maintenance.
"This notification is being made pursuant to 10 CFR 50.72(b)(3)(xiii)
"The NRC Resident Inspector has been notified."
* * * UPDATE AT 1739 EDT ON 10/18/11 FROM STEVE BREWER TO S. SANDIN * * *
The Duane Arnold Energy Center (DAEC) Technical Support Center (TSC) Emergency Diesel Generator (EDG) was returned to service at 1637 CDT on 10/18/11.
The licensee informed the NRC Resident Inspector. Notified R3DO (Daley).
"At 0450 (CDT), on October 18, 2011, the Duane Arnold Energy Center (DAEC) Technical Support Center (TSC) Emergency Diesel Generator (EDG) was removed from service for preplanned maintenance. The expected duration of the maintenance is 12 hours. Normal power to the TSC will be available for the duration of the maintenance.
"This notification is being made pursuant to 10 CFR 50.72(b)(3)(xiii)
"The NRC Resident Inspector has been notified."
* * * UPDATE AT 1739 EDT ON 10/18/11 FROM STEVE BREWER TO S. SANDIN * * *
The Duane Arnold Energy Center (DAEC) Technical Support Center (TSC) Emergency Diesel Generator (EDG) was returned to service at 1637 CDT on 10/18/11.
The licensee informed the NRC Resident Inspector. Notified R3DO (Daley).
Power Reactor
Event Number: 47351
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: JON LAUDENBACH
HQ OPS Officer: PETE SNYDER
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: JON LAUDENBACH
HQ OPS Officer: PETE SNYDER
Notification Date: 10/18/2011
Notification Time: 17:36 [ET]
Event Date: 10/18/2011
Event Time: 09:39 [CDT]
Last Update Date: 10/18/2011
Notification Time: 17:36 [ET]
Event Date: 10/18/2011
Event Time: 09:39 [CDT]
Last Update Date: 10/18/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
ROBERT DALEY (R3DO)
ROBERT DALEY (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
RANDOM FITNESS FOR DUTY TEST FAILURE
A non-licensed employee had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.
A non-licensed employee had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.
Power Reactor
Event Number: 47352
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAVID BUTLER
HQ OPS Officer: STEVE SANDIN
Region: 4 State: TX
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAVID BUTLER
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/18/2011
Notification Time: 18:21 [ET]
Event Date: 10/18/2011
Event Time: 15:45 [CDT]
Last Update Date: 10/18/2011
Notification Time: 18:21 [ET]
Event Date: 10/18/2011
Event Time: 15:45 [CDT]
Last Update Date: 10/18/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
VIVIAN CAMPBELL (R4DO)
VIVIAN CAMPBELL (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
ALUMINUM VALVE DISCOVERED INSTALLED IN CONTAINMENT
"While Unit 1 was in Mode 5, for the 15th refueling outage, an issue was identified with the valve material of an existing installed airlock hydraulic system valve. The valve was determined to have an aluminum body which is not suitable for safety related use in containment.
"The Unit 1 airlock hydraulic system penetrates the containment pressure boundary. The airlock hydraulic system achieves containment integrity by being a closed system under GDC-57. A loss of pressure boundary integrity would no longer meet General Design Criteria 57 (GDC-57) for a closed system.
"Aluminum is a restricted/limited material in containment because it is not compatible with accident conditions and has failures with multiple adverse effects. Due to this condition, the valve would potentially lose pressure integrity during a LOCA with containment spray actuation.
"Compensatory measures have been taken to prevent containment spray from affecting this valve and at this time, the airlock is operable.
"Luminant Power determined this issue to be reportable at 1545 [CDT] on 10/18 per 50.72(b)(3)(ii)(B) Comanche peak Unit 1 being in an unanalyzed condition that significantly degrades plant safety.
"The Unit 2 airlock is a different design and this condition does not apply to Unit 2."
This material was installed during original construction and discovered during a licensee self-assessment.
The licensee will notify the NRC Resident Inspector.
"While Unit 1 was in Mode 5, for the 15th refueling outage, an issue was identified with the valve material of an existing installed airlock hydraulic system valve. The valve was determined to have an aluminum body which is not suitable for safety related use in containment.
"The Unit 1 airlock hydraulic system penetrates the containment pressure boundary. The airlock hydraulic system achieves containment integrity by being a closed system under GDC-57. A loss of pressure boundary integrity would no longer meet General Design Criteria 57 (GDC-57) for a closed system.
"Aluminum is a restricted/limited material in containment because it is not compatible with accident conditions and has failures with multiple adverse effects. Due to this condition, the valve would potentially lose pressure integrity during a LOCA with containment spray actuation.
"Compensatory measures have been taken to prevent containment spray from affecting this valve and at this time, the airlock is operable.
"Luminant Power determined this issue to be reportable at 1545 [CDT] on 10/18 per 50.72(b)(3)(ii)(B) Comanche peak Unit 1 being in an unanalyzed condition that significantly degrades plant safety.
"The Unit 2 airlock is a different design and this condition does not apply to Unit 2."
This material was installed during original construction and discovered during a licensee self-assessment.
The licensee will notify the NRC Resident Inspector.